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ASME QME 1 : 2017

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

View Superseded by

QUALIFICATION OF ACTIVE MECHANICAL EQUIPMENT USED IN NUCLEAR FACILITIES

Available format(s)

Hardcopy , PDF

Superseded date

03-06-2023

Superseded by

ASME QME-1:2023

Language(s)

English

Published date

23-08-2017

€113.29
Excluding VAT

Foreword
Committee Roster
Organizaton of QME-1
Summary of Changes
Section QR - General Requirements
Mandatory Appendix to Section QR
QR-I - Qualification and Duties of Registered
       Professional Engineers for Certification Activities
Nonmandatory Appendices to Section QR
QR-A - Seismic Qualification of Active
       Mechanical Equipment
Appendix QR-A - Tables
QR-B - Guide for Qualification of Nonmetallic Parts
QR-C - Sample Registered Professional Engneer
       Certification Statements
Appendix QR-C Forms
Section QDR - Qualification of Dynamic Restraints
Mandatory Appendix to Section QDR
QDR-I - Qualification Specification for Dynamic Restraints
Nonmandatory Appendices to Section QDR
QDR-A - Restraint Similarity
QDR-B - Typical Values of Restraint Functional Parameters
Section QP - Qualification of Active Pump Assemblies
Mandatory Appendix to Section QP
QP-I - Qualification Specification for Active Pump Assemblies
Nonmandatory appendices to Section QP
AP-D - Pump Similarity Checklist
QP-E - Guidelines for Shaft-Seal System Material and
       Design Consideration
Appendix QP-E Tables
Section QV - Qualification Requirements for Active Valve
             Assemblies for Nuclear
Section QV Table
Mandatory Appendix to Section QV
QV-I - Qualification Specification for Active Valves
Nonmandatory Appendix to Section QV
QV-B - Static Side Load Testing for Power-Actuated
       and Relief Valve Assemblies
Section QVG - Guide to Section QV: Determination of
              Valve Assembly Performance Characteristics

Gives he requirements and guidelines for the qualification of active mechanical equipment whose function is required to ensure the safe operation or safe shutdown of a nuclear facility.

DocumentType
Standard
ISBN
978-0-7918-7155-3
Pages
128
PublisherName
American Society of Mechanical Engineers
Status
Superseded
SupersededBy
Supersedes

IEEE 382-2006 IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations
HI 1.6 : 2000 CENTRIFUGAL PUMP TESTS
HI 1.1-1.5 : 1994 CENTRIFUGAL PUMPS - NOMENCLATURE, DEFINITIONS, APPLICATIONS AND OPERATION
API 682 : 2014 PUMPS - SHAFT SEALING SYSTEMS FOR CENTRIFUGAL AND ROTARY PUMPS
ASCE 4 98 : 2000 SEISMIC ANALYSIS OF SAFETY-RELATED NUCLEAR STRUCTURES AND COMMENTARY
HI 9.1 - 9.5 : 2015 PUMPS - GENERAL GUIDELINES
IEEE 334 : 2007 QUALIFYING CONTINUOUS DUTY CLASS 1E MOTORS FOR NUCLEAR POWER GENERATING STATIONS
IEEE 344-2013 IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations
ANS 51.1-1983(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS
IEEE 101 : 1987 GUIDE FOR THE STATISTICAL ANALYSIS OF THERMAL LIFE TEST DATA
ASME OM : 2017 OPERATION AND MAINTENANCE OF NUCLEAR POWER PLANTS
ANS 52.1-83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS
IEEE 323-2003 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations
ASME PTC8.2 : 1990 PERFORMANCE TEST CODES - CENTRIFUGAL PUMPS
IEEE 627-2010 IEEE Standard for Qualification of Equipment Used in Nuclear Facilities
ASME B73.1 : 2012 SPECIFICATION FOR HORIZONTAL END SUCTION CENTRIFUGAL PUMPS FOR CHEMICAL PROCESS
ASME PV CODE 3 APP DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - APPENDICES
ASME B73.2 : 2016 Specification for Vertical In-Line Centrifugal Pumps for Chemical Process

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